• Nuclear Engineering and Technology
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• 제43권6호
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• pp.583-592
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• 2011

The radiological characteristics for waste classification were assessed for neutron-activated decommissioning wastes from a CANDU reactor. The MCNP/ORIGEN2 code system was used for the source term analysis. The neutron flux and activation cross-section library for each structural component generated by MCNP simulation were used in the radionuclide buildup calculation in ORIGEN2. The specific activities of the relevant radionuclides in the activated metal waste were compared with the specified limits of the specific activities listed in the Korean standard and 10 CFR 61. The time-average full-core model of Wolsong Unit 1 was used as the neutron source for activation of in-core and ex-core structural components. The approximated levels of the neutron flux and cross-section, irradiated fuel composition, and a geometry simplification revealing good reliability in a previous study were used in the source term calculation as well. The results revealed the radioactivity, decay heat, hazard index, mass, and solid volume for the activated decommissioning waste to be $1.04{\times}10^{16}$ Bq, $2.09{\times}10^3$ W, $5.31{\times}10^{14}\;m^3$-water, $4.69{\times}10^5$ kg, and $7.38{\times}10^1\;m^3$, respectively. According to both Korean and US standards, the activated waste of the pressure tubes, calandria tubes, reactivity devices, and reactivity device supporters was greater than Class C, which should be disposed of in a deep geological disposal repository, whereas the side structural components were classified as low- and intermediate-level waste, which can be disposed of in a land disposal repository. Finally, this study confirmed that, regardless of the cooling time of the waste, 15% of the decommissioning waste cannot be disposed of in a land disposal repository. It is expected that the source terms and waste classification evaluated through this study can be widely used to establish a decommissioning/disposal strategy and fuel cycle analysis for CANDU reactors.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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• pp.187-188
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• 2017

• 방사성폐기물학회지
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• 제7권1호
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• pp.63-72
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• 2009

방사성폐기물 처분에서 미생물에 대한 연구는 최근에 중요한 연구 결과들이 지속적으로 발표됨에 따라 그 중요성에 대한 인식이 차츰 확대되고 있는 추세이다. 본 연구에서는 방사성폐기물 처분에서 미생물의 역할과 영향들에 대한 연구결과 및 연구동향을 조사 분석하였다. 방사성폐기물 처분시스템에서 고려되고 있는 다중방벽들인 인공방벽과 자연방벽에서의 미생물들의 역할 및 연구결과를 정리하여 제시하였다. 인공방벽에서는 처분용기의 부식에 대한 영향과 압축된 완충재에서의 미생물의 생존가능성 및 역할에 대해 논의하였다. 천연방벽에서는 지하수 및 암반에 존재하는 미생물들의 역할을 자연유사연구 결과와 함께 정리하여 제시하였다. 또한 지하매질을 통한 핵종이동 및 지연특성에서 미생물의 역할과 다양한 작용과정들 및 영향을 최근 연구동향과 함께 분석하고 정리하여 제시하였다. 따라서 향후 심부 지하 환경에서 처분시스템의 거동 및 지중매질을 통한 방사성 핵종의 이동 등에 미치는 미생물의 영향에 대한 심도 있는 연구가 본격적으로 수행된다면 미생물의 중요성 및 역할에 대한 엄격한 평가를 할 수 있을 것으로 사료된다.

• 환경영향평가
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• 제28권3호
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• pp.312-331
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• 2019

해상최종처리장은 육상에서의 폐기물 처리 공간 부족 문제 해소와 친환경적인 해양공간 조성 및 개발을 목적으로 육 해상 폐기물 소각재 등 안정화된 무기성 고형 폐기물을 해상에서 최종 매립하는 폐기물 처리장을 의미한다. 본 연구의 목적은 현재까지 국내 조성 사례가 없는 해상최종처리장의 건설 시 해양환경에 어떠한 영향을 미치는지를 조사 예측 평가하고 환경영향에 대한 저감과 피해를 최소화하여, 사업 초기단계에서부터 충분한 환경적 고려가 반영된 해상최종처리장 건설 환경영향평가 가이드라인을 마련하고자 한다. 이를 위하여 국내 외 유사사례 환경영향평가서 및 기존 환경영향평가 가이드라인 사례 분석과 포럼 운영을 통한 전문가 검토 및 합의과정을 거쳐 해상최종처리장 건설에 특화된 가이드라인을 도출하였다. 국내 유사사례 환경영향평가서 검토를 위해서 총 17건의 준설토 투기장 및 발전소 회처리장 조성사업 환경영향평가서(2005~2016년)를 대상으로 해양 동 식물 및 해양수질 및 해양저질, 해양물리 항목의 조사현황을 분석하고 문제점과 개선안을 도출하였다. 본 가이드라인을 통해 과학적이고 체계적인 절차에 따라 환경영향평가가 수행될 수 있도록 지원함으로써 해양환경 피해를 최소화하고, 사업과 관련한 협의기간 단축 및 사회적 갈등 해소와 제반 경제적 비용 절감 등에 기여하고자 하였다.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2006년도 제32회 KOSCO SYMPOSIUM 논문집
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• pp.75-78
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• 2006

Disposal of highly toxic wastes like polychlorinated biphenyls (PCBs) is very difficult. These substances create a growing mountain of problematic waste that has to be disposed properly. Conventional technologies that are based on common burning(rotary kiln, ${\sim}1100^{\circ}C$) and plasma technology(${\sim}10000^{\circ}C$) do not satisfy important conditions. for example, complete combustion of the toxic waste and the price of waste disposal. The combustor like a rocket engine is operated at relatively high pressure(${\sim}15$ bar) and relatively high temperature(>$3000^{\circ}C$) that are ideal for the complete destruction of extremely toxic substances. In this study, test compound($_o-DCB$) was dissolved in kerosine with a concentration of 10%. Pure gas oxygen was used as an oxidant. Analysis showed that the destruction efficiency achieved for ${o}-DCB$ was 99.9999% or better. The results show that a combustor based on liquid propllant rocket technology is a validated tool for the disposal of highly toxic waste, and a good alternative technology when applied to the destruction of extremely toxic wastes.

• 한국지반환경공학회 논문집
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• 제2권1호
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• pp.15-22
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• 2001

고형화 폐기물의 처분에 대한 환경 위해성 평가의 핵심은 화학적 용출특성을 파악 후, 현장의 환경조건하에서 유해물질이 얼마나 주변환경으로 유출되는가를 예측하여 그 위해도를 산정하고, 그 위해도가 환경적으로 허용가능한 지를 판단하는 데 있다. 본 논문에서는 고형화폐기물을 매립지에 처분하거나 재활용시 다양한 현장조건하에서의 환경위해성을 평가하는 체계를 용출의 두 가지 극한적 경우에 입각하여 수립하였다. 수립된 위해성평가체계의 각 경우에 따른 폐기물 특성변수를 결정할 수 있는 두 종류의 특성평가기법을 개발하고, 시멘트 고화 처리된 도시쓰레기 소각재의 매립처분 현장에 적용하여 검증하였다.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3359-3366
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• 2021

An engineered barrier system (EBS) for the deep geological disposal of high-level radioactive waste (HLW) is composed of a disposal canister, buffer material, gap-filling material, and backfill material. As the buffer fills the empty space between the disposal canisters and the near-field rock mass, heat energy from the canisters is released to the surrounding buffer material. It is vital that this heat energy is rapidly dissipated to the near-field rock mass, and thus the thermal conductivity of the buffer is a key parameter to consider when evaluating the safety of the overall disposal system. Therefore, to take into consideration the sizeable amount of heat being released from such canisters, this study investigated the thermal conductivity of Korean compacted bentonites and its variation within a temperature range of 25 ℃ to 80-90 ℃. As a result, thermal conductivity increased by 5-20% as the temperature increased. Furthermore, temperature had a greater effect under higher degrees of saturation and a lower impact under higher dry densities. This study also conducted a regression analysis with 147 sets of data to estimate the thermal conductivity of the compacted bentonite considering the initial dry density, water content, and variations in temperature. Furthermore, the Kriging method was adopted to establish an uncertainty metamodel of thermal conductivity to verify the regression model. The R² value of the regression model was 0.925, and the regression model and metamodel showed similar results.

• 한국유기농업학회지
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• 제28권4호
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• pp.535-553
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• 2020

In this study, the characteristics of the waste sector CDM project were analyzed through cluster analysis of the waste sector CDM project and the analysis of the CDM investment cost in waste sector using CDM project data registered with UNFCCC since 2008 when EU ETS phase 2 began. As of September 2020, 772 cases of CDM projects in waste disposal and disposal are registered. Biogas technology is the largest, followed by livestock manure processing and biomass production technology. The results of the cluster analysis are summarized as follows: First, on average, projects utilizing AWMS technology are small in size and relatively low in investment costs. This is judged to be relatively low investment costs due to previously attracted foreign investment capital. Second, the average investment cost of CDM projects considered along with waste (No.13), the energy industry (No.1) and agriculture (No.15) was higher than those involving only waste. The analysis of the factors determining the investment cost of the waste sector CDM project showed that, as with cluster analysis, the AWMS technology, which is a livestock manure treatment technology, was lower in the investment cost than those that use other technologies. As a result of multiple regression analysis, the investment cost of the CDM project was analyzed lower in the order of biomass, AWMS, LFG and biogas. Also, the higher the investment cost for CDM projects linked to waste, energy and agriculture, and the better the investment environment, the higher the investment cost. Although no statistical feasibility was obtained, the larger the annual emission reduction, the lower the CDM investment cost.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.64-72
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• 2004

The dryer (ten per unit) are operating to remove tritium in PHWR(Pressurized Heavy Water Reactor). There are coming out heavy water adsorbent from operating the dryer (95 drums for ten year per unit) The amount of radioactivity of heavy water adsorbent almost exceed ninety times more than disposal limit-in-itself showed by The Ministry of Science and Technology. It has to be disposed whole radioactive waste products, however there are problems of increase at the expense of their permanent disposal. In this research, We have studied how to remove kinds of nuclear materials and amount of tritium with in heavy water adsorbent. As the result we could develop disposal equipment and apply it. D20 adsorbent have to contain below Gamma nuclide O.3Bq/g and tritium 100Bq/g "The Regulation for disposal of the radioactivity wastes" showed by The Ministry of Science and Technology. There fore. So as to remove amount of tritium and kinds of nuclear materials (DTO) we needed a equipment. Also we have studied how to remove effectively radioactivity with in Adsorbent. As cleaning heavy water adsorbent and drying on each condition (temperature for drying and hours for cleaning). Because there is something to return heavy water adsorbent by removing impurities within adsorbent when it is dried o high temperature. After operating, we have been applying this research to the way to dispose heavy water adsorbent. Through this we could reduce solid waste products and the expense of permanent disposal of radioactive waste products and also we could contribute nuclear power plant run safely. According to the result we could keep the best condition of radiation safety super vision and we could help people believe in safety with Radioactivity wastes control for harmony with Environment.

• 방사성폐기물학회지
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• 제6권4호
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• pp.387-398
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• 2008

원자력이용시설 주변의 방사선환경조사는 교육과학기술부 고시 제2008-28호(원자력이용시설 주변의 방사선환경조사 및 방사선환경 영향평가에 관한 고시)에 따라 주변주민들이 받게 되는 방사선량이 연간 선량한도 이내로 충분히 적게 유지되고 있는지를 확인함으로써 주변주민의 건강과 안전을 확보하고 주변 환경의 오염을 사전에 예방하는 데 있다. 그런데 국내 최초의 방사성폐기물처분시설은 시설운영을 시작하기 전 최소 2년 동안의 기초 환경조사 자료를 취득하여 부지주변의 기준 준위를 설정해야 하므로 2007년부터 2009년 상반기 방사성폐기물처분시설의 시범운영 및 2010년 상반기 준공을 목표로 방사선과 방사능에 대한 관한 기초 환경조사 자료를 취득하고 있다. 따라서 방사성폐기물처분시설 주변의 방사선환경조사에 관한 추진내용을 분석하고 최근에 취득한 2008년도 전반기 방사선환경조사결과를 바탕으로 향후 조사계획서 개정방향과 방사성폐기물처분시설 주변의 방사선환경조사를 수행하기 위해 관련 내용을 고찰하였다.